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Letter, Inspection Report  and Inspection Report Correspondence

Tin +  and Lead +

10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50 Appendix B Criterion XI +  and 10 CFR 50 Appendix B Criterion III, Design Control +

Emergency Preparedness +, Barrier Integrity +  and Mitigating Systems +

05000424  +, 05000425  +, 00424  +  and 00425  +

05000425/FIN-2007006-01 +, 05000425/FIN-2007006-02 +, 05000425/FIN-2007006-04 +  and 05000425/FIN-2007006-03 +

NRC/RGN-II/DRS/EB1 +  and Cain L +

NRC Generic Letter 98-02, Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition +  and NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +

ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +, ML072050572 +  and ML072050572 +

IEEE 308-1974 +  and IEEE-450 +

IP 71111.17 +, IP 71111.21 +  and IP 71111.02 +

Cutler-Hammer +, Westinghouse +  and General Electric +

NRC Bulletin 11-90 +  and NRC Bulletin 11-31 +

Information Notice 2006-18, Significant Loss of Safety-related Electrical Power at Forsmark, Unit 1, in Sweden +, Information Notice 90-25 +, Information Notice 95-03 +, Information Notice 07-14 +, Information Notice 2005-21, Plant Trip and Loss of Preferred AC Power from Inadequate Switchyard Maintenance +, Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines +  and Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station +

AOP +, ES-1.3 +, Emergency Operating Procedure +  and ES-1.1 +

X10E-6 +, 1X3D-BC-Q04B +, 1X3D-BC-F04A +, 07-40-425 +, X3CK03-C +, 1X3D-AA-A01A +, 1X3D-AA-B02A +, 1X3D-AA-C01A +, 1X3D-AA-D02A +, 1X3D-AA-D02B +, 1X3D-AA-F16A +, 1X3D-AA-F36A +, 1X3D-AA-G01A +, 1X3D-AA-H04A +, 1X3D-AA-M03A +, 1X3D-AA-M04A +, 1X3D-AA-M08A-13 +, 1X3D-AA-M08A-14 +, 1X3D-AA-M08A-15 +, 1X3D-AA-M08A-16 +, 1X3D-AA-M08A-17 +, 1X3D-AA-M08A-28 +, 1X3D-AA-MO8A-32 +, 1X3D-AA-M08A-35 +, 1X3D-AA-M08A-36 +, 1X3D-AA-M08A-37 +, 1X3D-AA-M08A-56 +, 1X3D-AA-K01A +, 1X3D-BA-D02B +, 1X3D-BA-D02D +...

Vogtle +  and NPF-68 +

Washington +  and Georgia +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Main Steam Line +, Safety Relief Valve +  and Main Steam +

Southern Nuclear +  and Tynan T +

Safe Shutdown +, Probabilistic Risk Assessment +, Job Performance Measure +, Loss of Offsite Power +, Time Critical Operator Action +, Battery sizing +, Overspeed trip +  and Overspeed +